Similar Documents at Maine Yankee |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20236T4711998-07-14014 July 1998 Application for Amend to License DPR-36,consisting of Proposed Change 209,amending TS to Revise Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing Requirements ML20216F8831998-04-13013 April 1998 Application for Amend to License DPR-36,consisting of Proposed Change 208,revising TS to Base LCO for Fuel Storage Pool on Revised Analysis for Fuel Handling Accident & on New Analysis for Radiological Shielding During Movement of Fuel ML20212A6021997-10-20020 October 1997 Application for Amend to License DPR-36,consisting of Proposed TS Change 207,reflecting Permanently Defueled Status of Plant ML20211H6691997-09-30030 September 1997 Application for Amend to License DPR-36,eliminating Conditions,No Longer Appropriate in Permanently Defueled Condition ML20210M5801997-08-15015 August 1997 Application for Amend to License DPR-36,consisting of TS Change 206,revising TS Re Facility Staffing & Training ML20136B5161997-03-0505 March 1997 Application for Amend to License DPR-36,requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant ML20134J6551997-02-0707 February 1997 Proposed TS Change 203 to License DPR-36,revising TS Pages 3.12-1,3.12-2 & 3.12-3 Re 115 Kv Offsite Power Requirements ML20134J6261997-02-0707 February 1997 Proposed TS Change 204 to License DPR-36,requesting one-time Extension of SG Tube Surveillance Interval as Specified in TS 4.10.C.2 ML20133A7011996-12-19019 December 1996 Application for Amend to License DPR-36,requesting Rev to Boronometer Operability Requirement & Reactor Coolant Boron Sampling ML20127P2191993-01-25025 January 1993 Application for Amend to License DPR-36,consisting of Proposed TS Change 177 to Allow Increase in Number of Spent Fuel Assemblies Stored in Spent Fuel Pool from 1,476 to 2,019.Rev 0 to Licensing Rept... Encl ML20126B6821992-12-15015 December 1992 Proposed TS Change 176 to License DPR-36,modifying TS 3.19 & 4.6 for Consistency W/Change in Normal Operating Position of LPSI motor-operated Isolation Valves from Closed to Open ML20198D0701992-05-0808 May 1992 Proposed TS Change 166 to License DPR-36,revising Section 1.4 to Eliminate Ref to Containment Air Recirculation Sys from TS 1.4.D, Containment Purge Sys ML20141M1121992-03-24024 March 1992 Application for Amend to License DPR-36,consisting of TS Proposed Change 165,revising Fuel Enrichment Limit & Allowing Radial & Axial Zoning of Enrichment Up to 3.95 Weight Percent U-235 ML20062D2801990-11-0505 November 1990 Application for Amend to License DPR-36,consisting of Proposed Change 151 Re Removal of cycle-specific Limits in Response to Generic Ltr 88-16 ML20058B5941990-10-15015 October 1990 Proposed Change 156 Requesting Amend to License DPR-36, Modifying Tech Spec 3.22, Feedwater Trip Sys, by Adding Exception Specifically Addressing Operation of Emergency Feedwater Sys During Plant Startups & Shutdowns ML20058L9271990-07-30030 July 1990 Application for Amend to License DPR-36,consisting of Proposed Change 154,revising Page 5.2-2 Re Manager Qualification Requirements for Operations ML20055G3101990-07-10010 July 1990 Application for Amend to License DPR-36,consisting of Tech Spec Change 155 Re Safety Injection Actuation Sys ML20055E0951990-07-0505 July 1990 Application for Amend to License DPR-36,consisting of Proposed Change 154,modifying Tech Specs Re Qualification Requirements for Operations Manager ML20235H5401989-02-15015 February 1989 Application for Amend to License DPR-36,consisting of Proposed Change 146,amending Tech Spec Sections 3.9 & 4.1 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouples Channel Operability ML20196B5261988-11-22022 November 1988 Application for Amend to License DPR-34,consisting of Proposed Change 134 Re Main Steam Excess Flow Check Valve. Amend Modifies Tech Spec 4.6 Re Periodic Testing by Extending Specified Surveillance Testing Interval ML20206F2281988-11-0808 November 1988 Application for Amend to License DPR-36,modifying Tech Spec 1.1, Fuel Storage. Fee Paid ML20205T2091988-11-0202 November 1988 Application for Approval to Leave Inplace,Slightly Contaminated Soil Next to Reactor Water Storage Tank. Radiological Assessment Encl.Fee Paid ML20206C2571988-10-26026 October 1988 Application for Amend to License DPR-36,amending Tech Spec Section 5.2 to Delete Offsite & Facility Organization Charts,Per Generic Ltr 88-06.Fee Paid ML20205M9611988-10-18018 October 1988 Application for Amend to License DPR-36,consisting of Proposed Change 133,modifying Specified Surveillance Interval for Control Element Assembly Partial Movement Test from Once Every 2 Wks to Monthly.Fee Paid ML20150E8971988-06-30030 June 1988 Application for Amend to License DPR-36,consisting of Proposed Change 141,revising Tech Specs to Reflect Cycle 11 Operation.Cycle 11 Core Performance Analysis Rept Encl.Fee Paid ML20150E4071988-03-24024 March 1988 Application for Amend to License DPR-36,increasing Max Nominal Fuel Enrichment from 3.5% to 3.7% U-235.Fee Paid ML20147G8921988-03-0101 March 1988 Application for Amend to License DPR-36,modifying Tech Spec 5.2 to Reflect Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure.Fee Paid ML20235A6781988-01-0606 January 1988 Application for Amend to License DPR-36,consisting of Proposed Change 135,revising Offsite & Facility Organizational Charts.Fee Paid ML20236G4941987-07-30030 July 1987 Application for Amend to License DPR-36,consisting of Proposed Change 132,replacing Tech Specs Page 3.10-4 Re Core Operation Increase Flexibility When Incore Monitoring Sys Inoperable.Fee Paid ML20216B8301987-06-23023 June 1987 Application for Amend to License DPR-36,consisting of Proposed Change 131,revising Tech Specs Page 5.8-1 Re Process Control Program.Fee Paid ML20212K9831987-02-24024 February 1987 Application for Amend to License DPR-36,consisting of Proposed Change 130,reflecting Revised LOCA Limits.Fee Paid ML20212D9141987-02-24024 February 1987 Application for Amend to License DPR-36,consisting of Proposed Change 126,changing Tech Specs 5.9.1.6 & 5.9.1.7 Re Semiannual Radioactive Effluent Release Repts & Special Repts,Respectively.Fee Paid ML20212L1511987-01-13013 January 1987 Application for Amend to License DPR-36,consisting of Suppl 1 to Proposed Change 113,revising Tech Specs Re RCS Emergency Vent Sys,Per NUREG-0737,Item II.B.1 ML20207P5151987-01-12012 January 1987 Application for Amend to License DPR-36,consisting of Proposed Change 128 to Tech Specs Supporting Cycle 10 Operation.Significant Hazards Consideration & Summary Description of Tech Spec Changes Encl.Fee Paid ML20215C2321986-12-0808 December 1986 Addendum to 860207 Application for Amend to License DPR-36, Consisting of Suppl 1 to Proposed Change 109 Re Limiting Overtime of Staff Personnel ML20214N0101986-11-25025 November 1986 Application for Amend to License DPR-36,consisting of Proposed Change 125,revising Tech Specs to Increase Max Nominal Fuel Enrichment from 3.30 to 3.50 Weight % U-235. Significant Hazards Evaluation Encl.Fee Paid ML20212C0211986-07-29029 July 1986 Application for Amend to License DPR-36,consisting of Proposed Change 124,revising Tech Specs Re Reporting Requirements for Primary Coolant Sys Iodine Spikes,Per Generic Ltr 85-19.Related Info Encl.Fee Paid ML20203F1251986-07-16016 July 1986 Application for Amend to License DPR-36,consisting of Proposed Change 119,revising Tech Specs to Remove Cycle Reload Specific Parameters & Introducing Peaking Factor Limit Rept.Fee Paid ML20203Q3031986-05-0505 May 1986 Application for Amend to License DPR-36,incorporating Proposed Change 122,revising Tech Specs Turbine Valve Test Frequencies.Supporting Documentation Encl.Fee Paid ML20204A3771986-05-0505 May 1986 Suppl 2 to Proposed Change 114 to License DPR-36,revising Tech Spec 3.11.5 to Add Five Manual Isolation Valves to List of Manual Containment Isolation Valves That May Be Respositioned W/O Implementing Compensatory Measures ML20151U4501986-02-0303 February 1986 Application for Amend to License DPR-36,consisting of Suppl 1 to Proposed Change 109,adding Administrative Controls on Limiting Overtime of Personnel & Removing Offsite & Onsite Organizational Charts from Tech Spec 5.2 ML20137Q8991986-01-29029 January 1986 Application for Amend to License DPR-36,consisting of Proposed Change 115,adopting Model for LER Reporting Requirements Re Iodine Spikes in Primary Coolant,Per Generic Ltr 85-19.Fee Paid ML20138M5891985-12-16016 December 1985 Application for Amend to License NPF-36,consisting of Suppl 2 to Proposed Change 120,revising Tech Specs to Incorporate Limiting Condition for Operations for turbine-driven Auxiliary Feedwater Pump ML20138P6271985-12-13013 December 1985 Application for Amend to License DPR-36,consisting of Suppl 1 to Proposed Change 110,revising Tech Spec Pages 4.6-1,4.6-3 Through 4.6-6 & 4.1-9 Re Emergency Feedwater Sys ML20138H0631985-12-0909 December 1985 Application for Amend to License DPR-36,consisting of Proposed Change 118,allowing Consideration of Fire Hazards in Vicinity of Affected Penetration When Determining Level of Compensatory Fire Protection.Fee Paid ML20133K5741985-10-16016 October 1985 Application for Amend to License DPR-36,consisting of Proposed Change 121,deleting Present Tech Spec Requirement for Emergency Diesel Generator Testing in Event That Any Component in One Train of Cooling Sys Inoperable.Fee Paid ML20133F4301985-10-0707 October 1985 Application for Amend to License DPR-36,consisting of Proposed Change 114,Suppl 1,changing Tech Spec Pages 3.11-2 & 3.11-5 Re Containment Isolation Valves Under Administrative Controls ML20133C2051985-10-0303 October 1985 Application for Amend to License DPR-36,consisting of Suppl 1 to Proposed Change 120,replacing Pages of Tech Specs Re turbine-driven Auxiliary Feedwater Pump ML20205C7821985-09-12012 September 1985 Application for Amend to License DPR-36,consisting of Suppl 2 to Proposed Change 81,revising Tech Specs Re Shock Suppressors ML20135E0251985-09-0606 September 1985 Application for Amend to License DPR-36,consisting of Proposed Change 120,changing Tech Specs to Require Turbine Auxiliary Feedwater Pump Be Operable During Facility Operation.Fee Paid 1998-07-14
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20206H1521999-05-0505 May 1999 Amend 164 to License DPR-36,deleting License Conditions 2.B.6.c,2.B.6.e,2.B.6.f,2.B.6.g,2.B.7(a) & 2.B.7(b) Which Are No Longer Applicable Due to Permanently Shutdown & Defueled Condition of Plant ML20206G5681999-05-0303 May 1999 Amend 163 to License DPR-36,revising Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20204C4561999-03-16016 March 1999 Amend 162 to License DPR-36,revising App a TS of License DPR-36 to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet ML20236T4711998-07-14014 July 1998 Application for Amend to License DPR-36,consisting of Proposed Change 209,amending TS to Revise Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing Requirements ML20216F8831998-04-13013 April 1998 Application for Amend to License DPR-36,consisting of Proposed Change 208,revising TS to Base LCO for Fuel Storage Pool on Revised Analysis for Fuel Handling Accident & on New Analysis for Radiological Shielding During Movement of Fuel ML20217H4991998-03-30030 March 1998 Amend 161 to License DPR-36,replacing App A,Ts to License DPR-36 in Entirety ML20202D3121997-11-26026 November 1997 Amend 160 to License DPR-36,revising Selected Portions of Plant TS 5.0 to Define Facility Staffing & Training Requirements for Permanently Shutdown & Defueled Facility ML20212A6021997-10-20020 October 1997 Application for Amend to License DPR-36,consisting of Proposed TS Change 207,reflecting Permanently Defueled Status of Plant ML20211H6691997-09-30030 September 1997 Application for Amend to License DPR-36,eliminating Conditions,No Longer Appropriate in Permanently Defueled Condition ML20210M5801997-08-15015 August 1997 Application for Amend to License DPR-36,consisting of TS Change 206,revising TS Re Facility Staffing & Training ML20216F1291997-08-0808 August 1997 Amend 159 to License DPR-36,revising TS 5.5.B to Designate President of Maine Yankee as Responsible Official for Matters Re Nuclear Safety Audit & Review Committee ML20141G6301997-05-19019 May 1997 Amend 158 to License DPR-36,revising TS to Permit Use of 10CFR50,App J,Option B,performance-based Containment Leakage Rate Testing ML20138G3401997-05-0202 May 1997 Amend 157 to License DPR-36,revising TS 3.12, Station Svc Power, to Require Both 115 Kv Power Circuits to Be Operable When Reactor Critical ML20136B5161997-03-0505 March 1997 Application for Amend to License DPR-36,requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant ML20134J6551997-02-0707 February 1997 Proposed TS Change 203 to License DPR-36,revising TS Pages 3.12-1,3.12-2 & 3.12-3 Re 115 Kv Offsite Power Requirements ML20134J6261997-02-0707 February 1997 Proposed TS Change 204 to License DPR-36,requesting one-time Extension of SG Tube Surveillance Interval as Specified in TS 4.10.C.2 ML20133A7011996-12-19019 December 1996 Application for Amend to License DPR-36,requesting Rev to Boronometer Operability Requirement & Reactor Coolant Boron Sampling ML20058E2561993-11-0505 November 1993 Amend 143 to License DPR-36,modifying TS 4.6.A Re Safety Injection & Containment Spray Sys,To Require Quarterly,Vice Monthly,Testing of Automatic Core Flooding & Containment Spray Valves ML20056G9321993-09-0101 September 1993 Corrected TS Page 4.5-1 to Amend 140 to License DPR-36 ML20056F7821993-08-23023 August 1993 Amend 142 to License DPR-36,deleting Surveillance Requirements for Environ Monitors from TS ML20127P2191993-01-25025 January 1993 Application for Amend to License DPR-36,consisting of Proposed TS Change 177 to Allow Increase in Number of Spent Fuel Assemblies Stored in Spent Fuel Pool from 1,476 to 2,019.Rev 0 to Licensing Rept... Encl ML20127D4881993-01-11011 January 1993 Amend 136 to License DPR-36,modifying Remedial Action Requirements of TS 3.6.B & 3.6.C,by Deleting Alternate Train Testing Requirements ML20126H6071992-12-29029 December 1992 Amend 135 to License DPR-36,making Two Corrections to Core Operating Limits Presented in TS 5.14.1 ML20126B6821992-12-15015 December 1992 Proposed TS Change 176 to License DPR-36,modifying TS 3.19 & 4.6 for Consistency W/Change in Normal Operating Position of LPSI motor-operated Isolation Valves from Closed to Open ML20126C0981992-12-0909 December 1992 Errata to Amend 134 for License DPR-36,correcting Item 2 to Page One ML20198D0701992-05-0808 May 1992 Proposed TS Change 166 to License DPR-36,revising Section 1.4 to Eliminate Ref to Containment Air Recirculation Sys from TS 1.4.D, Containment Purge Sys ML20141M1121992-03-24024 March 1992 Application for Amend to License DPR-36,consisting of TS Proposed Change 165,revising Fuel Enrichment Limit & Allowing Radial & Axial Zoning of Enrichment Up to 3.95 Weight Percent U-235 ML20062D2801990-11-0505 November 1990 Application for Amend to License DPR-36,consisting of Proposed Change 151 Re Removal of cycle-specific Limits in Response to Generic Ltr 88-16 ML20058B5941990-10-15015 October 1990 Proposed Change 156 Requesting Amend to License DPR-36, Modifying Tech Spec 3.22, Feedwater Trip Sys, by Adding Exception Specifically Addressing Operation of Emergency Feedwater Sys During Plant Startups & Shutdowns ML20059D0381990-08-30030 August 1990 Amend 117 to License DPR-36,modifying Tech Spec 3.14, Primary Sys Leakage, by Deleting Current Limit of 1.0 Gpm from All Steam Generator Tubes & Establishing 0.15 Gpm from Any One Steam Generator ML20058L9271990-07-30030 July 1990 Application for Amend to License DPR-36,consisting of Proposed Change 154,revising Page 5.2-2 Re Manager Qualification Requirements for Operations ML20055G3101990-07-10010 July 1990 Application for Amend to License DPR-36,consisting of Tech Spec Change 155 Re Safety Injection Actuation Sys ML20055E0951990-07-0505 July 1990 Application for Amend to License DPR-36,consisting of Proposed Change 154,modifying Tech Specs Re Qualification Requirements for Operations Manager ML20246L4291989-07-14014 July 1989 Revised Pages 3.10-16 & 3.10-17 to Amend 107 to License DPR-36,correcting Typos ML20246F6231989-07-10010 July 1989 Amend 113 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Operation ML20245D4451989-04-24024 April 1989 Amend 111 to License DPR-36,changing Moderator Temp Coefficient Limit in Tech Specs Between 0% & 30% Power Levels ML20245D4341989-04-24024 April 1989 Amend 112 to License DPR-36,modifying Tech Spec Table 3.9-3, Accident Monitoring Instrumentation & Table 4.1-3 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouple Channel Operability ML20235H5401989-02-15015 February 1989 Application for Amend to License DPR-36,consisting of Proposed Change 146,amending Tech Spec Sections 3.9 & 4.1 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouples Channel Operability ML20196B5261988-11-22022 November 1988 Application for Amend to License DPR-34,consisting of Proposed Change 134 Re Main Steam Excess Flow Check Valve. Amend Modifies Tech Spec 4.6 Re Periodic Testing by Extending Specified Surveillance Testing Interval ML20206F2281988-11-0808 November 1988 Application for Amend to License DPR-36,modifying Tech Spec 1.1, Fuel Storage. Fee Paid ML20205T2091988-11-0202 November 1988 Application for Approval to Leave Inplace,Slightly Contaminated Soil Next to Reactor Water Storage Tank. Radiological Assessment Encl.Fee Paid ML20206C2571988-10-26026 October 1988 Application for Amend to License DPR-36,amending Tech Spec Section 5.2 to Delete Offsite & Facility Organization Charts,Per Generic Ltr 88-06.Fee Paid ML20205M9611988-10-18018 October 1988 Application for Amend to License DPR-36,consisting of Proposed Change 133,modifying Specified Surveillance Interval for Control Element Assembly Partial Movement Test from Once Every 2 Wks to Monthly.Fee Paid ML20207L6021988-10-11011 October 1988 Correction to Amend 106 to License DPR-36,replacing Tech Spec Page 3.12-1 ML20155B4501988-09-27027 September 1988 Amend 107 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Reload Core ML20154A1311988-09-0707 September 1988 Amend 106 to License DPR-36,modifying Tech Spec 3.12 Re Station Svc Power by Prohibiting Reliance on 115 Kv Suroweic Line Unless Addl Justification Provided to NRC ML20150E8971988-06-30030 June 1988 Application for Amend to License DPR-36,consisting of Proposed Change 141,revising Tech Specs to Reflect Cycle 11 Operation.Cycle 11 Core Performance Analysis Rept Encl.Fee Paid ML20196G6801988-06-23023 June 1988 Amend 105 to License DPR-36,changing Max Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core for Operating Cycle 11 & Beyond from 3.5 to 3.7% Nominal Weight U-235 ML20151W5731988-04-26026 April 1988 Amend 104 to License DPR-36,revising Tech Spec Figures 5.2-1 & 5.2-2 to Reflect Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure ML20150E4071988-03-24024 March 1988 Application for Amend to License DPR-36,increasing Max Nominal Fuel Enrichment from 3.5% to 3.7% U-235.Fee Paid 1999-05-05
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MaineYankee RF LI ABL E E L E CT RICIT Y SINCE 197?
329 Bath Road Charles D. Fnzzle February 7. 1997 Brunswick. Maine 04o11 President and Chief Executive Officer MN-97-30 CDF-97-24 (207) 798-4100 Proposed Change No. 204 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington. DC 20555
Reference:
(a) License No. DPR-36 (Dorket No. 50-309)
(b) USNRC Letter to MYAPC dated June 1. 1995. " Summary of May 11.
1995. Meeting on Maine Yankee Steam Generator Inspections and Plans for Repair" ;
(c) MYAPC Letter to USNRC dated December 19, 1995 (MN-95-139). l
" Steam Generator Tube Surveillance" (d) MYAPC Letter to USNRC dated November 29.1995 (MN-95-132)
" Proposed Technical Specification Change No. 169 - Steam Generator Leakage and Tube Surveillance Requirements"
Subject:
Proposed Technical Specification Change No. 204 Maine Yankee Steam Generator Tube Surveillance Requirements Gentlemen:
Maine Yankee hereby submits, pursuant to 10CFR50.90, this application to amend sections of the Maine Yankee Technical Specifications. This proposed change requests a one-time extension of the Steam Generator Tube Surveillance interval as specified in Technical Specification 4.10.C.2.
As a result of an unusually long refueling and maintenance outage in 1995 and two limited-scope outages during the current operating cycle. the next refueling outage has been re-scheduled for no earlier than September 1997 and possibly not )
until early 1998. During the 1995 refueling and maintenance outage (from J February to May). Maine Yankee conducted extensive steam generator tube surveillances. In response to the surveillance results. Maine Yankee conducted a tube sleeving program which was completed by December 10. 1995. Therefore, a l conservative calculation.of the due date for conducting the next required steam l
generator surveillance, including a 25 percent allowance in accordance with i }
Technical Specification 4.0.A.. indicates that it should occur by June of 1997..
prior to the next scheduled refueling outage. 1 Maine Yankee has evaluated the proposed change and has determined that it does not: involve a significant increase in the probability or consequences of an accident previously evaluated; create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety. Therefore, the proposed change does not involve a significant hazards consideration as defined in 10 CFR 50.92. The evaluation is included in Attachment A.
9702120224 970207 PDR ADOCK 05000309 P PDR g
MaineYankee l
UNITED STATES NUCLEAR REGULATORY COMMISSION MN-97-30 l Attention: Document Control Desk Page Two Revised Technical Specification Page 4.10-2 is included as Attachment B.
Attachment C is provided to allow for efficient processing should proposed change no.169 be approved and issued prior to the approval and issuance of this proposed change.
This proposed change has been reviewed and approved by the Plant Operating Review Committee. The Nuclear Safety Audit and Review Committee has also reviewed this submittal. A representative of the State of Maine is being informed of this request by a copy of this letter.
We request that the review of this proposed change and the issuance of a Facility l License Amendment be completed by June 1997. Accordingly, we request that the i amendment become effective immediately upon issuance.
l Very truly yours.
Charles D. Frizzle )
President and Chief Executive Officer Attachments MAW /mwf c: Mr Hubert J. Miller Mr. J. T. Yerokun Mr. P. J. Dostie Mr. Clough Toppan Mr. Uldis Vanags Mr. D. H. Dorman l
STATE OF MAINE l
Then personally appeared before me Charles D. Frizzle, who being duly sworn did state that he is President and Chief Executive Officer of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the b st of his kno ledge and belief.
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i l ATTACHMENT A
SUMMARY
DESCRIPTION OF THE PROPOSED CHANGF,S MQ j SIGNIFICANT HAZARDS EVALUATION I
1 i
i l
ATTACHMENT A !
SIGNIFICANT HAZARDS EVALUATION ,
! Descriotion of Prooosed Chance The proposed change to Technical Specification 4.10 Steam Generator Tube !
j Surveillance provided in Attachment B would allow a one-time extension of !
the Steam Generator Tube Surveillance interval as specified in Technical ;
i Specification 4.10.C.2. This Technical Specification requires that the l inspection frequency be increased to at least once per 20 months if the :
results of the inservice inspection of a steam generator-fall in Category '
C-3 as defined in Technical Specification 4.10.B.
i As a result of an unusually long refueling and maintenance outage in 1995 1
and two limited-scope outages during the current operating cycle the next refueling outage has been re-scheduled for no earlier than September 1997
- and possibly not until early 1998.' During the 1995 refueling and
- maintenance outage (from February to May), Maine Yankee conducted j extensive steam generator tube surveillances. The results of this
, surveillance were presented to the NRC at a public meeting in Rockville.
1 Maryland on May ll. 1995 and were documented as an attachment to Reference (b). The surveillance results placed all three Steam Generators in Category C-3. In response to the surveillance results, Maine Yanket conducted a tube sleeving program which was completed by December 10.
1995. The number of tubes plugged or sleeved in each steam generator was reported to the NRC in Reference (c).
A conservative calculation of the due date for conducting the next required steam generator surveillance can be determined by setting the start of the interval in May 1995. This due date, including a 25 percent allowance in accordance with Technical Specification 4.0. A. , is June 1997.
which is prior to the next refueling outage as re-scheduled. Therefore.
Maine Yankee is requesting an extension of the steam generator tube surveillance interval to the next refueling outage or not later than March
- 31. 1998. whichever is earlier.
Safety Assessment This proposed Technical Specification change was prompted by the extended periods of unit downtime during the current fuel cycle and the extent of unit downtime taken to implement the steam generator tube sleeving repairs during the 1995 refueling and maintenance outage following the completion of the eddy current examination conducted in accordance with the tube surveillance program as described in Technical Specification 4.10. This unit downtime has resulted in the liklihood that the 20 ( 25 percent) calendar month surveillance interval may elapse prior to the next scheduled refueling outage. This proposed change does not change the bases of the technical specification.
Page A-1
a ATTACHMENT A SIGNIFICANT HAZARDS EVALUATION Safety Assessment (Continuedl Furthermore, the total " inservice" time before the next inspection, defined as the cumulative time during the current cycle when the steam generators actively performed the heat removal function, will not exceed 20 months under this proposed change.
Each of the three steam generators at Maine Yankee is a Combustion Engineering supplied, vertical U-tube heat exchanger, designed in accordance with the ASME Boiler and Pressure Vessel Code.Section III.
Class A. Each steam generator is designed with 5703 tubes made of a nickel-chromium-iron alloy.
Steam Generator (SG) tubes are part of the reactor coolant system pressure boundary. SG tube surveillance requirements, including inspection interval limits were est 3blished to ensure that the structural integrity of that portion of the reactor coolant system will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83. Revision 1. The inservice inspection requirements were specified in order to detect and monitor evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube or tube sleeve degradation so that' corrective measures can be'taken.
During the 1995 refueling and maintenance outage extensive eddy current inspections of the steam generators were performed including:
100% full length Bobbin (incluaing tubes deplugged for sleeving purposes) in each of the three SG's.
. 100% Motorized Rotating Pancake Coil (MRPC) on the hot leg tube sheet expansion transition zone in each of the three SG's.
100% MRPC on the cold leg tube sheet expansion transition zone in each of the three SG's, and 100% MRPC on the tightest radius U-bend (tube rows 1 through 12 inclusive) in each of the three SG's.
In addition, the following diagnostic inspection were performed on a portion of the SG tubing for further analysis: Plus Point ECT.
fluorescent penetrant, in-situ hydrostatic testing, lamb wave ultrasonic.
CECC0 ECT and tube pulls.
Page A-2 1
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ATTACHMENT A ;
I
, SIGNIFICANT HAZARDS EVALUATION i
i Safety Assessment (Continued) i l In response to these eddy current inspection results.100% of the tube sheet hot leg transition area for tubes left in-service in each SG were sleeved. Following the SG tube sleeving repairs. each in service sleeve was eddy current tested using the CECCO-5 probe. The combination of
- extensive eddy current examinations and full scale sleeving of the tube ;
i sheet hot leg transition area for tubes left in service, provides a '
- sufficient degree of confidence that the condition of the steam generator tubes was fully understood to the degree allowed by the state-of-the-art j eddy-current technology and that the steam generators were returned to j
service in a condition free from unrepaired defects.
- During the current operating cycle. the primary and secondary coolant l systems have been operated within their respective chemistry limits.
Defects are unlikely to have occurred and are unlikely to occur during the
,' period of the requested surveillance interval extension.
Maine Yankee has observed minimum primary to secondary leakage in its i steam generators during this cycle. Also. Maine Yankee's low l administrative and proposed Technical Specification (Reference d) steam i generator leakage limits of 50 and 150 GPD respectively. should ensure i Maine Yankee shuts down and makes repairs before the stress in any tube exceeds its design criteria.
Sionificant Hazards Evaluation The proposed change to the Technical Specifications has been evaluated j against the standards of 10 CFR 50.92 and has been determined to not i involve a significant hazards consideration. The proposed change does not:
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- 1. Involve a significant increase in the probability or consequences of j an accident previously evaluated.
Since the extension time will not increase the total in-service time experienced by the Steam Generators during the current cycle before the next inspection and since the primary and secondary coolant !
chemistry performance, steam generator primary-to-secondary leakrate :
performance during the current cycle have been well within their l respective limits and since there is no significant pressure or temperature effect during the shutdown mode, the likelihood that a tube or tubes will degrade will not significantly increase.
Furthermore the combination of extensive eddy current examinations and full scale sleeving of the tube sheet hot leg transition area for tubes left in service during the 1995 refueling and maintenance outage, provides a sufficient degree of confidence that the condition of the steam generator tubes was fully understood to the degree allowed by the state-of-the-art eddy-current technology and ;
that the steam generators were returned to service in a condition '
free from unrepaired defects.
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i ATTACHMENT A 11GNIFICANT HAZARDS EVALUATION i
The proposed change, therefore. does not significantly increase the probability or consequences of any previously evaluated accident.
- 2. Create the possibility of a new or different kind of accident from !
any accident previously evaluated.
There are no new failure modes associated with the proposed Technical Specification change. Since the plant will continue to ;
operate as designed during the surveillance extension period, the ;
proposed change will not modify the plant response. '
Therefore, inclusion of the proposed change -in the Technical i Specifications would not create the possibility of a new or s different kind of accident from any previously evaluated.
- 3. Involve a significant reduction in a margin of safety. l Since steam generator tube degradation occurs primarily during i operation, the surveillance interval extension should have no or .
little effect on the rate of progression of tube degradation since !
the total in-service time experienced by the steam generators will not increase. :
Therefore, adoption of the proposed change would not involve a significant reduction in safety margin for the plant.
Maine Yankee has concluded that the proposed change to the Technical :
Specifications does not involve a significant hazards consideration as !
defined by 10 CFR 50.92.
1 1pformation Concernina an Environmental Assessment An Environmental Assessment is not required for the Technical Specification changes proposed by this Proposed Change because the requested changes to the Maine Yankee Technical Specifications meet the criteria for " actions eligible for categorical exclusion" as specified in 10CFR51.22(c)(9). The requested changes will have no impact on the envirc 'clent. The changes do riot involve a Significant Hazards Consideration as discussed in the preceding section. The requested changes do not involve a significant change in the types or significant increase in the amounts of any effluent that may be released off-site. Also, the requested changes do not involve a significant increase in individual or cumulative occupational radiation exposure.
Conclusion i Therefore based upon the reasoning presented above. Maine Yankee has determined that the requested change does not involve a significant hazards consideration.
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